ML20034A921
| ML20034A921 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/17/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034A922 | List: |
| References | |
| NUDOCS 9004250068 | |
| Download: ML20034A921 (9) | |
Text
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DUKE POWER COMPANY DOCKET NO. 50 369 i
McGUIRE NUCLEAR STATION, UNIT 1 1
AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.107 License No. NpF-9 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the liqensee) dated February 15, 1990, as supplemented March 19, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I-B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and reculations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and l
sefety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.107, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR RE0VLATORY COMMISSION yik Up
',/n David B. Matthews, Director
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Project Directorate 11-3 Division of Reactor Projects-l/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: April 17,1990
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DUKE POWER COMPANY DOCKET NO. 50-370 McGU1RE NUCLEAR STAT 10N. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No,89 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station Unit 2(thefacility)FacilityOperatingLicenseNo.NPF-17Iiled by the Duke Power Company (the licensee) dated February 15, 1990, as supplemented March 19, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and +.he rules and regulations of the Comission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby this amendment ran be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon i
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
1
2 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 89. are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMIS$10N mum ~ N
/,3 David B. Hat hews, Director
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Project Directorate 11 3 Division of Reactor Projects-1/11 Office of Nuclear Reacter Regulation l
Attachment:
l Technical Specification Changes Date of Issuance: April 17, 1990 l
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ATTACHMENT TO LICENSE AMENDMENT NO.107 FACILITY OPERATING LICENSE NO NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 89 FACILITY OPEPATING LICENSE NO. NPF-17 00CKET NO. 50-370 Peplace the following peges of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages and new page are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Pages insert Pages 3/4 4-14 3/4 4-14 3/4 4-15 3/4 4-15 B 3/4 4-3 B 3/4 A-3 B 3/4 4-3e (acw page) l i
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4 4.4.5.4 Acceptance Criteria a.
As used in this specification:
1)
Imperfection means an exception to the dimensions, finish or contour of a tube or sleeve from that required by fabrication l
drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube or sleeve wall thickness, if l
detectable, may be considered as imperfections; 2)
Deoradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve; 3)
Deoraded Tube means a tube or sleeve containing imperfections greater than or equal to 20% of the nominal tube or sleeve wall thickness caused by degradatiory; 4)
% degradation means the percentage of the tube or sleeve wall l
thickness affected or removed by degradation; 5)
Defect means an imperfection of such severity that it exceeds i
the repair limit.
A tube or sleeve containing a defect is l
l defective; 6)
Repair Limit means the imperfection depth at or beyond which the tube or sleeve sball be removed from service by plugging or repaired by sleevir,g and is equal to 40% of the nominal tube or sleeve wall thickness.
This definition does not apply to the area of the tubesheet region below the F* distance provided the tube is not degraded (i.e., no indications of cracking) within the F* distance.
If a tube is sleeved due to degradation in the F* distance, then any defects in the tube below the sleeve will remain in service without repair.
The Babcock & Wilcox process (or method) equivalent to the method described in Topical Report BAW-2045(P)-A will be used.
7)
Unserviceable describes the condition of a tube or sleeve if it l
leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3c, above; 8)
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg; and McGUIRE - UNITS 1 and 2 3/4 4-14 Amendment No 107 (Unit 1)
Amendment No. 89 (Unit 2)
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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 9)
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing.
This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
10)
F* Distance is the distance into the tubesheet from the top face of the tubesheet or the top of the last hardroll, whichever is lower (further into the tubesheet) that has been conservatively chosen to be 2 inches.
11)
F* TUBE is a tube with degradation equal to or greater than 40%,
below the F* distance and not degraded (i.e., no indications of cracking) in the F* distance, b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the repair l
limit and all tubes containing through-wall cracks) required by Table 4.4-2, 4.4.5.5 Reports Within 15 days following the completion of each inservice inspection a.
of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2; b.
The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.
This Special Report shall include:
1)
Number and extent of tubes inspected, 2)
Location and percent of wall-thickness penetration for each indication of an imperfection, and 3)
Identification of tubes plugged or repaired.
l c.
The results of inspections of F* tubes shall be reported to the Commission in a report, prior to the restart of the unit following the inspection.
This report shall include:
1)
Identification of F* tubes, and 2)
Location and size of the degradation.
McGUIRE - UNITS 1 and 2 3/4 4-15 Amendment No.107 (Unit 1)
Amendment No. 89(Unit 2) j
REACTOR COOLANT SYSTEM BASES 3/4.4.4 RELIEF VALVES The power-operated relief valves (PORVs) and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump.
Operation of the PORVs minimizes l
the undesirable opening of the spring-loaded pressurizer code safety valves.
Each PORV has a remotely operated block valve to provide a positive shutoff capability should a relief valve become inoperable.
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be main-tained.
The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
The B&W process (or method) equivalent to the inspection method described in Topical Report BAW-2045(P)-A will be used.
Inservice inspection of steam generator sleeves is also required to ensure RCS integrity.
Because the sleeves introduce changes in the wall thickness and diameter, they reduce the sensitivity of eddy current testing, therefore, special inspection methods must be used.
A method is described in Topical Report BAW-2045(P)-A with supporting validation data that demonstrates the inspectability of the sleeve and underlying tube.
As required by NRC for licensees authorized to use this repair process, McGuire commits to validate the adequacy of any system that is used for periodic inservice inspections of the sleeves, and will evaluate and, as deemed appropriate by Duke Power Company, implement testing methods as better methods are developed and validated for commercial use.
The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking.
The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the Reactor Coolant System and the Secondary Coolant System (reactor-to-secondary leakage = 500 gallons per day per steam generator).
Cracks having a reactor-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents.
Operating plants have demonstrated that reactor-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown.
Leakage in excess of this limit will require plant Amendment No.107 (Unit 1)
McGUIRE - UNITS I and 2 B 3/4 4-3 Amendment No. 89 (Unit 2)
BASES 3/4.4.5 STEAM GENERATORS (Continued) shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.
Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.
However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.
Repair will be required for all tubes with imperfections exceeding the repair limit of 40% of the tube nominal wall thickness.
Installed sleeves with imper-fections exceeding 40% of the sleeve nominal wall thickness will be plugged.
Defective steam generator tubes can be repaired by the installation of sleeves which span the area of degradation, and serve as a replacement pressure boundary for the degraded portion of the tube, allowing the tube to remain in service.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect wastage type degradation that has penetrated 20%
of the original tube wall thickness.
For tubes with degradation below the F*
distance, and not degraded within the F* distahce, repair is not required.
If a tube is sleeved due to degradation in the F* distance, then any defects in the tube below the sleeve will remain in service without repair.
Amendment No.107(Unit 1)
McGUIRE - UNITS 1 and 2 B 3/4 4-3a Amendment No. 89(Unit 2)
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